Sfoglia per Rivista NUCLEAR ENGINEERING AND DESIGN
European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems
2015-01-01 Bandini, G.
Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility
2019-01-01 Lorusso, P.; Pesetti, A.; Tarantino, M.; Narcisi, V.; Giannetti, F.; Forgione, N.; Del Nevo, A.
Experimental campaign on the HLM loop NACIE-UP with instrumented wire-spaced fuel pin simulator
2018-01-01 Di Piazza, I.
Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility
2015-01-01 Del Nevo, A.
Experimental investigation on powder conductivity for the application to double wall heat exchanger (NACIE-UP)
2015-01-01 Tarantino, M.; Di Piazza, I.; Fasano, G.
Experimental tests and post-test analysis of non-uniformly heated 19-pins fuel bundle cooled by Heavy Liquid Metal
2019-01-01 Marinari, R.; Di Piazza, I.; Tarantino, M.; Angelucci, M.; Martelli, D.
Extension of the sub-channel code ANTEO+ to the mixed convection regime
2017-01-01 Grasso, G.
Fully developed turbulent convection of Lead Bismuth Eutectic in the elementary cell of the NACIE-UP Fuel Pin Bundle
2020-01-01 Angeli, D.; Di Piazza, I.; Marinari, R.; Stalio, E.
Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility
2016-01-01 Tarantino, M.; Di Piazza, I.
HLM fuel pin bundle experiments in the CIRCE pool facility
2015-01-01 Tarantino, M.; Di Piazza, I.
Improvement of ALFRED thermal hydraulics through experiments and numerical studies
2023-01-01 Caramello, M.; Frignani, M.; Grasso, G.; Tarantino, M.; Martelli, D.; Lorusso, P.; Di Piazza, I.
In-containment source term predictability of ASTEC-Na: Major insights from data-predictions benchmarking
2017-01-01 Mascari, F.
Melting temperature of MOX fuel for FBR applications: TRANSURANUS modelling and experimental findings
2015-01-01 Calabrese, R.
Mixed convection and stratification phenomena in a heavy liquid metal pool
2015-01-01 Tarantino, M.; Di Piazza, I.
Monte Carlo simulation analysis of integral data measured in the SCK-CEN/ENEA experimental campaign on the TAPIRO fast reactor. Experimental and calculated data comparison
2014-01-01 Santagata, A.; Peluso, V.; Burgio, N.
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)
2013-01-01 Sarotto, M.
NACIE-UP post-test simulations by CFD codes
2020-01-01 Pucciarelli, A.; Barone, G.; Forgione, N.; Galleni, F.; Martelli, D.
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor
2018-01-01 Lodi, F.; Sarotto, M.; Grasso, G.
Numerical analyses of the CIRCE-THETIS facility by mean of STH and CFD codes
2023-01-01 Stefanini, P.; Pucciarelli, A.; Forgione, N.; Di Piazza, I.; Martelli, D.
Overview of the independent ASTEC V2.0 validation by SARNET partners
2014-01-01 Bandini, G.
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